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Title: Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR

Abstract

Experimental and modeling investigations on the DIII-D and EAST tokamaks show the attractive transport and stability properties of fully noninductive, high poloidal-beta (β P) plasmas, and their suitability for steady-state operating scenarios in ITER and CFETR. A key feature of the high-β P regime is the large-radius (r>0.6) internal transport barrier (ITB), often observed in all channels (ne, Te, Ti, rotation), and responsible for both excellent energy confinement quality and excellent stability properties. Experiments on DIII-D have shown that, with a largeradius ITB, very high β N and β P values (both≥4) can be reached by taking advantage of the stabilizing effect of a nearby conducting wall. Synergistically, higher plasma pressure provides turbulence suppression by Shafranov shift, leading to ITB sustainment independent of the plasma rotation. Experiments on EAST have been used to assess the long pulse potential of the high-β P regime. Using RF-only heating and current drive, EAST achieved minute-long fully noninductive steady state H-mode operation with strike points on an ITER-like tungsten divertor. Improved confinement (relative to standard H-mode) and steady state ITB features are observed with a monotonic q-profile with q min~1.5. Separately, experiments have shown that increasing the density in plasmas driven by lower hybridmore » wave broadens the q-profile, a technique that could enable a large radius ITB. These experimental results have been used to validate MHD, current drive, and turbulent transport models, and to project the high-β P regime to a burning plasma. These projections suggest the Shafranov shift alone will not suffice to provide improved confinement (over standard H-mode) without rotation and rotation shear. However, increasing the negative magnetic shear (higher q on axis) provides a similar turbulence suppression mechanism to Shafranov shift, and can help devices such as ITER and CFETR achieve their steady-state fusion goals.« less

Authors:
ORCiD logo [1];  [2]; ORCiD logo [2];  [2];  [3]; ORCiD logo [2];  [2];  [2];  [2];  [2];  [4]; ORCiD logo [4];  [5];  [6];  [7]; ORCiD logo [2];  [2];  [6];  [8];  [2] more »;  [9];  [10];  [10];  [1];  [2];  [1];  [2];  [2]; ORCiD logo [2];  [2];  [2] « less
  1. General Atomics, San Diego, CA (United States)
  2. Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics
  3. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  4. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  5. Columbia Univ., New York, NY (United States)
  6. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  7. Huazhong Univ. of Science and Technology, Wuhan (China)
  8. Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA), Saint-Paul-Les-Durance (France)
  9. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
  10. Univ. of California, Los Angeles, CA (United States). Dept. of Physics and Astronomy
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1502029
Report Number(s):
LLNL-JRNL-758197
Journal ID: ISSN 0741-3335; 943646
Grant/Contract Number:  
AC52-07NA27344
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Plasma Physics and Controlled Fusion
Additional Journal Information:
Journal Volume: 60; Journal Issue: 1; Journal ID: ISSN 0741-3335
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats

Garofalo, A. M., Gong, X. Z., Ding, S. Y., Huang, J., McClenaghan, J., Pan, C. K., Qian, J., Ren, Q. L., Staebler, G. M., Chen, J., Cui, L., Grierson, B. A., Hanson, J. M., Holcomb, C. T., Jian, X., Li, G., Li, M., Pankin, A. Y., Peysson, Y., Zhai, X., Bonoli, P., Brower, D., Ding, W. X., Ferron, J. R., Guo, W., Lao, L. L., Li, K., Liu, H., Lyv, B., Xu, G., and Zang, Q. Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR. United States: N. p., 2017. Web. doi:10.1088/1361-6587/aa8c9d.
Garofalo, A. M., Gong, X. Z., Ding, S. Y., Huang, J., McClenaghan, J., Pan, C. K., Qian, J., Ren, Q. L., Staebler, G. M., Chen, J., Cui, L., Grierson, B. A., Hanson, J. M., Holcomb, C. T., Jian, X., Li, G., Li, M., Pankin, A. Y., Peysson, Y., Zhai, X., Bonoli, P., Brower, D., Ding, W. X., Ferron, J. R., Guo, W., Lao, L. L., Li, K., Liu, H., Lyv, B., Xu, G., & Zang, Q. Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR. United States. doi:10.1088/1361-6587/aa8c9d.
Garofalo, A. M., Gong, X. Z., Ding, S. Y., Huang, J., McClenaghan, J., Pan, C. K., Qian, J., Ren, Q. L., Staebler, G. M., Chen, J., Cui, L., Grierson, B. A., Hanson, J. M., Holcomb, C. T., Jian, X., Li, G., Li, M., Pankin, A. Y., Peysson, Y., Zhai, X., Bonoli, P., Brower, D., Ding, W. X., Ferron, J. R., Guo, W., Lao, L. L., Li, K., Liu, H., Lyv, B., Xu, G., and Zang, Q. Thu . "Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR". United States. doi:10.1088/1361-6587/aa8c9d. https://www.osti.gov/servlets/purl/1502029.
@article{osti_1502029,
title = {Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR},
author = {Garofalo, A. M. and Gong, X. Z. and Ding, S. Y. and Huang, J. and McClenaghan, J. and Pan, C. K. and Qian, J. and Ren, Q. L. and Staebler, G. M. and Chen, J. and Cui, L. and Grierson, B. A. and Hanson, J. M. and Holcomb, C. T. and Jian, X. and Li, G. and Li, M. and Pankin, A. Y. and Peysson, Y. and Zhai, X. and Bonoli, P. and Brower, D. and Ding, W. X. and Ferron, J. R. and Guo, W. and Lao, L. L. and Li, K. and Liu, H. and Lyv, B. and Xu, G. and Zang, Q.},
abstractNote = {Experimental and modeling investigations on the DIII-D and EAST tokamaks show the attractive transport and stability properties of fully noninductive, high poloidal-beta (βP) plasmas, and their suitability for steady-state operating scenarios in ITER and CFETR. A key feature of the high-βP regime is the large-radius (r>0.6) internal transport barrier (ITB), often observed in all channels (ne, Te, Ti, rotation), and responsible for both excellent energy confinement quality and excellent stability properties. Experiments on DIII-D have shown that, with a largeradius ITB, very high βN and βP values (both≥4) can be reached by taking advantage of the stabilizing effect of a nearby conducting wall. Synergistically, higher plasma pressure provides turbulence suppression by Shafranov shift, leading to ITB sustainment independent of the plasma rotation. Experiments on EAST have been used to assess the long pulse potential of the high-βP regime. Using RF-only heating and current drive, EAST achieved minute-long fully noninductive steady state H-mode operation with strike points on an ITER-like tungsten divertor. Improved confinement (relative to standard H-mode) and steady state ITB features are observed with a monotonic q-profile with qmin~1.5. Separately, experiments have shown that increasing the density in plasmas driven by lower hybrid wave broadens the q-profile, a technique that could enable a large radius ITB. These experimental results have been used to validate MHD, current drive, and turbulent transport models, and to project the high-βP regime to a burning plasma. These projections suggest the Shafranov shift alone will not suffice to provide improved confinement (over standard H-mode) without rotation and rotation shear. However, increasing the negative magnetic shear (higher q on axis) provides a similar turbulence suppression mechanism to Shafranov shift, and can help devices such as ITER and CFETR achieve their steady-state fusion goals.},
doi = {10.1088/1361-6587/aa8c9d},
journal = {Plasma Physics and Controlled Fusion},
issn = {0741-3335},
number = 1,
volume = 60,
place = {United States},
year = {2017},
month = {11}
}

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